2017-2019 年 WEST 运行期间散装钨分流器部件前缘裂纹的实验表征

IF 2.3 2区 物理与天体物理 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Materials and Energy Pub Date : 2024-09-24 DOI:10.1016/j.nme.2024.101746
M. Diez , J. Demiane , P. Reilhac , D. Dorow-Gerspach , M.Lemetais , J. Gerardin , J. Gaspar , C. Martin , A. Durif , M. Wirtz , T. Loewenhoff , the WEST team
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引用次数: 0

摘要

在 2017-2019 年 WEST 运行期间,在下部分流器上安装了一套由钨单体组成的类似于热核实验堆的等离子体面单元。尽管加热功率不大,但这些单块中仍有 27% 在没有环形斜面保护的极边前缘出现了裂纹。对这 133 个出现裂纹的单体进行的全面实验分析表明,损坏发生在等离子体撞击点区域附近,在这些区域可以观察到在极边方向上相距 0.15-0.5 毫米的整齐裂纹。裂纹长达 1 毫米,深达 1 毫米,但不影响下分流器维持长脉冲的能力。影响裂纹形成的最重要参数是部件之间的相对垂直偏差。
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Experimental characterization of leading edge cracking on bulk tungsten divertor components during 2017–2019 WEST operation
During the 2017–2019 WEST operation, a set of ITER-like plasma-facing units consisting of tungsten monoblocks was installed on the lower divertor. Despite modest heating power, 27 % of these monoblocks had cracks on their poloidal leading edges, which were not protected by a toroidal bevel. A comprehensive experimental characterization of the 133 cracked monoblocks indicates that damage occurs near the plasma strike point areas where neat cracks separated by 0.15–0.5 mm in the poloidal direction were observed. Cracks are up to 1 mm long and 1 mm deep and did not affect the lower divertor ability to sustain long pulses. The most important parameter affecting crack formation is the relative vertical misalignment between components.
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来源期刊
Nuclear Materials and Energy
Nuclear Materials and Energy Materials Science-Materials Science (miscellaneous)
CiteScore
3.70
自引率
15.40%
发文量
175
审稿时长
20 weeks
期刊介绍: The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. Nuclear Materials and Energy publishes original research articles of up to 6 pages in length.
期刊最新文献
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